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Study of relation between the gamma flux buildup factors and source geometry by M-C simulation 被引量:1
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作者 Ali Rasouli hossein tavakoli-anbaran 《Nuclear Science and Techniques》 SCIE CAS CSCD 2017年第9期31-35,共5页
This paper is to achieve a gamma-ray source with the lowest rate of buildup factor, which is of great importance in medical, industrial and agricultural sciences.The flux buildup factor of gamma rays is calculated by ... This paper is to achieve a gamma-ray source with the lowest rate of buildup factor, which is of great importance in medical, industrial and agricultural sciences.The flux buildup factor of gamma rays is calculated by the MCNP code for point, linear, surface and volume sources with shield layers of lead, iron and aluminum. The results show that for the high Z shielding material, the flux buildup factor of coaxial cylindrical sources is the lowest(1.6–2.3)of all sources, while for low Z shielding materials, the coaxial disk surface sources have smaller buildup factor(1.45–1.6). 展开更多
关键词 通量 几何 模拟 增强因子 Γ射线源 农业科学 MCNP 伽马射线
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Designing a nuclear battery based on the Mo-99 radioactive source soluble in water and aqua regia in order to use in early tests 被引量:1
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作者 Zohreh Movahedian hossein tavakoli-anbaran 《Nuclear Science and Techniques》 SCIE CAS CSCD 2019年第3期37-45,共9页
Today, millions of electrocommunication, electric, medical, and industrial devices use battery. Batteries with long life and high energy density seem to be essential in medical, military, oil and mining, aerospace are... Today, millions of electrocommunication, electric, medical, and industrial devices use battery. Batteries with long life and high energy density seem to be essential in medical, military, oil and mining, aerospace areas as well as conditions in which access is difficult and in situations where replacement or recharging of battery is costly.In this regard, the use of radiation energy resulting from radioactive materials and its conversion to electric energy can be effective in making batteries. In the present study,various Mo-99 radioisotope values with a half-life of 65.98 h were used as a soluble radioactive source in two materials of water and aqua regia. Then, by comparing the results of the Monte Carlo simulations program MCNPX for these two solutions, it was found that when the water is used instead of aqua regia(for idealization), the values of the superficial current of electrons, the volumetric flux of electrons, and the deposited energy in the volume containing the radioactive solution increased by 10.80, 4.10,and 13.80%, respectively. Also, the short-circuit current and energy conversion efficiency of this battery with a concentration of 0.01 molar, Mo-99 dissolved in the aqua regia are 0.79μA and 16.47%, respectively. 展开更多
关键词 NUCLEAR battery RADIOACTIVE solution MCNPX code Mo-99
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